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{{#Wiki_filter:}} | {{#Wiki_filter:November 14, 2002 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) | ||
Richland, WA 99352-0968 | |||
==SUBJECT:== | |||
COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT RE: AMENDMENT REQUEST TO REVISE THE MINIMUM EMERGENCY DIESEL GENERATOR OUTPUT VOLTAGE (TAC NO. MB5672) | |||
==Dear Mr. Parrish:== | |||
The Commission has issued the enclosed Amendment No. 181 to Facility Operating License No. NPF-21 for the Columbia Generating Station (CGS). The amendment consists of changes to the Technical Specifications (TS) in response to your application dated July 16, 2002, as supplemented by letter dated September 4, 2002. | |||
The amendment revises Surveillance Requirements (SRs) 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 to change the specified minimum emergency diesel generator steady-state output voltage from 3740 volts to 3910 volts. | |||
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice. | |||
Sincerely, | |||
/RA/ | |||
Brian Benney, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397 | |||
==Enclosures:== | |||
: 1. Amendment No. 181 to NPF-21 | |||
: 2. Safety Evaluation cc w/encls: See next page | |||
November 14, 2002 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) | |||
Richland, WA 99352-0968 | |||
==SUBJECT:== | |||
COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT RE: AMENDMENT REQUEST TO REVISE THE MINIMUM EMERGENCY DIESEL GENERATOR OUTPUT VOLTAGE (TAC NO. MB5672) | |||
==Dear Mr. Parrish:== | |||
The Commission has issued the enclosed Amendment No. 181 to Facility Operating License No. NPF-21 for the Columbia Generating Station (CGS). The amendment consists of changes to the Technical Specifications (TS) in response to your application dated July 16, 2002, as supplemented by letter dated September 4, 2002. | |||
The amendment revises Surveillance Requirements (SRs) 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 to change the specified minimum emergency diesel generator steady-state output voltage from 3740 volts to 3910 volts. | |||
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice. | |||
Sincerely, | |||
/RA/ | |||
Brian Benney, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397 | |||
==Enclosures:== | |||
: 1. Amendment No. 181 to NPF-21 | |||
: 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION: | |||
PUBLIC RidsNrrLAEPeyton JCalvo PDIV-2 Reading RidsOgcRp BJones, RIV RidsNrrDlpmPdiv (WRuland) RidsAcrsAcnwMailCenter GHill (2) | |||
SDembek WBeckner RidsNrrPMBBenney TS: ML023190159 NRR-100 PKG.: ML023190526 ACCESSION NO.: ML022800463 NRR-058 *SE dated September 26, 2002 OFFICE PDIV-2/PM PDIV-2/LA EEIB/SC* OGC - NLO PDIV-2/SC NAME BBenney:rkb EPeyton CHolden RWeisman SDembek DATE 10/24/02 10/17/02 9/26/02 4 Nov 2002 11/13/02 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022800463.wpd OFFICIAL RECORD COPY | |||
Columbia Generating Station cc: | |||
Mr. Rodney L. Webring (Mail Drop PE04) Mr. Dale Atkinson (Mail Drop PE08) | |||
Vice President, Nuclear Generation Vice President, Technical Services Energy Northwest Energy Northwest P.O. Box 968 P.O. Box 968 Richland, WA 99352-0968 Richland, WA 99352-0968 Mr. Albert E. Mouncer (Mail Drop 1396) Thomas C. Poindexter, Esq. | |||
Vice President, Corporate Services/ Winston & Strawn General Counsel/CFO 1400 L Street, N.W. | |||
Energy Northwest Washington, DC 20005-3502 P.O. Box 968 Richland, WA 99352-0968 Mr. Bob Nichols Executive Policy Division Chairman Office of the Governor Energy Facility Site Evaluation Council P.O. Box 43113 P.O. Box 43172 Olympia, WA 98504-3113 Olympia, WA 98504-3172 Ms. Lynn Albin Mr. D. W. Coleman (Mail Drop PE20) Washington State Department of Health Manager, Performance Assessment P.O. Box 7827 and Regulatory Programs Olympia, WA 98504-7827 Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Ms. Christine Perrino (Mail Drop PE20) | |||
Manager, Licensing Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Chairman Benton County Board of Commissioners P.O. Box 69 Prosser, WA 99350-0190 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 69 Richland, WA 99352-0069 | |||
ENERGY NORTHWEST DOCKET NO. 50-397 COLUMBIA GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 181 License No. NPF-21 | |||
: 1. The Nuclear Regulatory Commission (the Commission) has found that: | |||
A. The application for amendment by Energy Northwest (licensee) dated July 16, 2002, as supplemented by letter dated September 4, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied. | |||
: 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows: | |||
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. | |||
: 3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance. | |||
FOR THE NUCLEAR REGULATORY COMMISSION | |||
/RA/ | |||
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation | |||
==Attachment:== | |||
Changes to the Technical Specifications Date of Issuance: November 14, 2002 | |||
ATTACHMENT TO LICENSE AMENDMENT NO. 181 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness. | |||
REMOVE INSERT 3.8.1-6 3.8.1-6 3.8.1-8 3.8.1-8 3.8.1-10 3.8.1-10 3.8.1-11 3.8.1-11 3.8.1-14 3.8.1-14 3.8.1-16 3.8.1-16 3.8.1-17 3.8.1-17 | |||
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 181TO FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397 | |||
==1.0 INTRODUCTION== | |||
By letter dated July 16, 2002, as supplemented by letter dated September 4, 2002, Energy Northwest (the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-21) for the Columbia Generating Station (CGS). The proposed changes would revise Surveillance Requirements (SRs) 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 to change the specified minimum emergency diesel generator (EDG) steady-state output voltage from 3740 volts to 3910 volts. | |||
The September 4, 2002, supplemental letter provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 20, 2002 (67 FR 53985). | |||
==2.0 REGULATORY EVALUATION== | |||
General Design Criterion (GDC)-17, "Electric Power System," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that a nuclear power plant have an onsite and offsite electric power system to permit the functioning of structures, systems and components important to safety. The onsite system is required to have sufficient independence, redundancy and testability to perform its safety function, assuming a single failure, and the offsite system is required to be supplied by two independent circuits. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as the result of loss of power from the unit, the offsite transmission network, or the onsite power supplies. GDC-18, "Inspection and Testing of Electric Power System," requires, in part, that electric power systems important to safety be designed to permit appropriate periodic inspection and testing. | |||
At CGS, the EDGs provide a source of emergency power when offsite power is either unavailable or is insufficiently stable to allow safe plant operation. The Division 1 and 2 standby alternating current (AC) power sources consist of two independent 4.16 kV Class 1E diesel generators, each connected to one of the two 4.16 kV Class 1E switchgear buses via two main circuit breakers. One breaker is located near the diesel generator unit; the other is located in the 4.16 kV Class 1E switchgear. | |||
The Division 3 standby ac power source, which is the source for the high pressure core spray system, consists of one independent 4.16 kV Class 1E diesel generator with its own 4.16 kV Class 1E switchgear bus. | |||
During the course of an NRC inspection in September of 2001 at CGS, a finding was identified that was one of very low safety significance and was characterized as a non-cited violation. | |||
The details of the finding are documented in NRC Inspection Report 50-397/01-06. In summary, it was found that the EDG output voltage range specified in SR 3.8.1.19.c.3 is from 3740V to 4400V and the degraded emergency bus voltage instrumentation allowable value range specified in Loss Of Power (LOP) Instrumentation Table 3.3.8.1-1.1.e is from 3685V to 3755V. This presents a condition wherein the TS allow a steady-state minimum EDG output voltage that is 15V lower than the maximum setpoint at which degraded voltage instruments may be actuated to perform their safety function. | |||
To reconcile the overlap between the two allowable ranges and provide consistent allowable output voltage ranges for all EDGs, the licensee proposes to increase the minimum steady-state EDG output voltage limit to 3910V for the Division 1, 2 and 3 EDGs. | |||
==3.0 TECHNICAL EVALUATION== | |||
The three EDGs at CGS specify the minimum steady-state output voltage for a loaded EDG to be 3740 V. This is based on American National Standard Institute (ANSI) Standard C84.1-1970 for normal utilization voltage for a 4kV medium voltage distribution system. However, if the degraded voltage instruments are set near the upper end of their acceptable range and the output voltage of the Division 1 and Division 2 diesels (EDG 1, EDG 2) is at the lower end of the acceptable range, the degraded voltage instrumentation could actuate and trip all loads off the Division 1 and Division 2 critical buses during a loss of offsite power and/or a loss of coolant accident. | |||
Critical bus loads include residual heat removal pumps, low pressure core spray pumps, service water pumps, and other equipment necessary to mitigate accident conditions. | |||
The licensee proposes to use 3910V as a minimum steady-state EDG output voltage for all three EDGs. This value is the minimum voltage necessary to meet the breaker closure (ready to load) interlock for EDG 1 and EDG 2, and it is the minimum EDG output voltage specified by the TS for unloaded EDGs. This proposed new steady-state voltage will be used in TS SRs 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 that currently specify a minimum steady-state output voltage of 3740V. This will reconcile the overlap between the two allowable ranges and is acceptable. | |||
EDG 3 is different in that it uses an 850 RPM speed interlock for its breaker closure permissive. | |||
However, it is reasonable to select 3910 V as an appropriate minimum steady-state voltage for EDG 3 since it is a dedicated power source for only one engineered safety feature load, and its bus voltage does not fluctuate as loads are sequenced on. Additionally, changing the minimum steady-state voltage specification for EDG 3 to 3910V (or 94 percent of a nominal 4160V) provides more margin to the analytical limit for the degraded voltage relay dropout and ensures that the EDG supplies a more conservative voltage to start the high pressure core spray pump | |||
motor (75 percent voltage is the minimum specified voltage needed at the motor terminals to start and accelerate the pump motor). This is acceptable. | |||
The staff finds that the proposed change is conservative and does not involve a design change or physical change to the equipment or the actual performance parameters of the diesel generators. There will be no change in the method of operation or in the way operability is demonstrated. The designs of CGSs EDGs feature precise regulation of output voltage using a Class 1E static exciter voltage regulator that controls generator output voltage to within +/-1% | |||
of its setpoint and the setpoint for the loss of power instrumentation is also controlled to within | |||
+/-1%. The proposed amendment does not involve a change to the margin between these two parameters and therefore is acceptable. | |||
The AC systems will continue to perform their safety functions in accordance with GDC-17. | |||
The changes will maintain the necessary level of systems reliability as it reconciles the overlap between the two allowable ranges of the degraded voltage instrumentation and the minimum steady-state EDGs output voltage. Therefore, the proposed changes to the technical specifications are acceptable. | |||
==4.0 STATE CONSULTATION== | |||
In accordance with the Commission's regulations, the Washington State Official was notified of the proposed issuance of the amendment. The State official had no comments. | |||
==5.0 ENVIRONMENTAL CONSIDERATION== | |||
The amendment changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 53985). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. | |||
==6.0 CONCLUSION== | |||
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. | |||
Principal Contributor: S. Saba Date: November 14, 2002}} |
Latest revision as of 08:35, 26 March 2020
ML022800463 | |
Person / Time | |
---|---|
Site: | Columbia ![]() |
Issue date: | 11/14/2002 |
From: | Brian Benney NRC/NRR/DLPM/LPD4 |
To: | Parrish J Energy Northwest |
Benney B, NRR/DLPM, 415-3764 | |
Shared Package | |
ml023190526 | List: |
References | |
TAC MB5672 | |
Download: ML022800463 (9) | |
Text
November 14, 2002 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT RE: AMENDMENT REQUEST TO REVISE THE MINIMUM EMERGENCY DIESEL GENERATOR OUTPUT VOLTAGE (TAC NO. MB5672)
Dear Mr. Parrish:
The Commission has issued the enclosed Amendment No. 181 to Facility Operating License No. NPF-21 for the Columbia Generating Station (CGS). The amendment consists of changes to the Technical Specifications (TS) in response to your application dated July 16, 2002, as supplemented by letter dated September 4, 2002.
The amendment revises Surveillance Requirements (SRs) 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 to change the specified minimum emergency diesel generator steady-state output voltage from 3740 volts to 3910 volts.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Brian Benney, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosures:
- 1. Amendment No. 181 to NPF-21
- 2. Safety Evaluation cc w/encls: See next page
November 14, 2002 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION - ISSUANCE OF AMENDMENT RE: AMENDMENT REQUEST TO REVISE THE MINIMUM EMERGENCY DIESEL GENERATOR OUTPUT VOLTAGE (TAC NO. MB5672)
Dear Mr. Parrish:
The Commission has issued the enclosed Amendment No. 181 to Facility Operating License No. NPF-21 for the Columbia Generating Station (CGS). The amendment consists of changes to the Technical Specifications (TS) in response to your application dated July 16, 2002, as supplemented by letter dated September 4, 2002.
The amendment revises Surveillance Requirements (SRs) 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 to change the specified minimum emergency diesel generator steady-state output voltage from 3740 volts to 3910 volts.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions next biweekly Federal Register notice.
Sincerely,
/RA/
Brian Benney, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosures:
- 1. Amendment No. 181 to NPF-21
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrLAEPeyton JCalvo PDIV-2 Reading RidsOgcRp BJones, RIV RidsNrrDlpmPdiv (WRuland) RidsAcrsAcnwMailCenter GHill (2)
SDembek WBeckner RidsNrrPMBBenney TS: ML023190159 NRR-100 PKG.: ML023190526 ACCESSION NO.: ML022800463 NRR-058 *SE dated September 26, 2002 OFFICE PDIV-2/PM PDIV-2/LA EEIB/SC* OGC - NLO PDIV-2/SC NAME BBenney:rkb EPeyton CHolden RWeisman SDembek DATE 10/24/02 10/17/02 9/26/02 4 Nov 2002 11/13/02 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML022800463.wpd OFFICIAL RECORD COPY
Columbia Generating Station cc:
Mr. Rodney L. Webring (Mail Drop PE04) Mr. Dale Atkinson (Mail Drop PE08)
Vice President, Nuclear Generation Vice President, Technical Services Energy Northwest Energy Northwest P.O. Box 968 P.O. Box 968 Richland, WA 99352-0968 Richland, WA 99352-0968 Mr. Albert E. Mouncer (Mail Drop 1396) Thomas C. Poindexter, Esq.
Vice President, Corporate Services/ Winston & Strawn General Counsel/CFO 1400 L Street, N.W.
Energy Northwest Washington, DC 20005-3502 P.O. Box 968 Richland, WA 99352-0968 Mr. Bob Nichols Executive Policy Division Chairman Office of the Governor Energy Facility Site Evaluation Council P.O. Box 43113 P.O. Box 43172 Olympia, WA 98504-3113 Olympia, WA 98504-3172 Ms. Lynn Albin Mr. D. W. Coleman (Mail Drop PE20) Washington State Department of Health Manager, Performance Assessment P.O. Box 7827 and Regulatory Programs Olympia, WA 98504-7827 Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Ms. Christine Perrino (Mail Drop PE20)
Manager, Licensing Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Chairman Benton County Board of Commissioners P.O. Box 69 Prosser, WA 99350-0190 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 69 Richland, WA 99352-0069
ENERGY NORTHWEST DOCKET NO. 50-397 COLUMBIA GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 181 License No. NPF-21
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Energy Northwest (licensee) dated July 16, 2002, as supplemented by letter dated September 4, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stephen Dembek, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 14, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 181 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3.8.1-6 3.8.1-6 3.8.1-8 3.8.1-8 3.8.1-10 3.8.1-10 3.8.1-11 3.8.1-11 3.8.1-14 3.8.1-14 3.8.1-16 3.8.1-16 3.8.1-17 3.8.1-17
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 181TO FACILITY OPERATING LICENSE NO. NPF-21 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NO. 50-397
1.0 INTRODUCTION
By letter dated July 16, 2002, as supplemented by letter dated September 4, 2002, Energy Northwest (the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-21) for the Columbia Generating Station (CGS). The proposed changes would revise Surveillance Requirements (SRs) 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 to change the specified minimum emergency diesel generator (EDG) steady-state output voltage from 3740 volts to 3910 volts.
The September 4, 2002, supplemental letter provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 20, 2002 (67 FR 53985).
2.0 REGULATORY EVALUATION
General Design Criterion (GDC)-17, "Electric Power System," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that a nuclear power plant have an onsite and offsite electric power system to permit the functioning of structures, systems and components important to safety. The onsite system is required to have sufficient independence, redundancy and testability to perform its safety function, assuming a single failure, and the offsite system is required to be supplied by two independent circuits. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as the result of loss of power from the unit, the offsite transmission network, or the onsite power supplies. GDC-18, "Inspection and Testing of Electric Power System," requires, in part, that electric power systems important to safety be designed to permit appropriate periodic inspection and testing.
At CGS, the EDGs provide a source of emergency power when offsite power is either unavailable or is insufficiently stable to allow safe plant operation. The Division 1 and 2 standby alternating current (AC) power sources consist of two independent 4.16 kV Class 1E diesel generators, each connected to one of the two 4.16 kV Class 1E switchgear buses via two main circuit breakers. One breaker is located near the diesel generator unit; the other is located in the 4.16 kV Class 1E switchgear.
The Division 3 standby ac power source, which is the source for the high pressure core spray system, consists of one independent 4.16 kV Class 1E diesel generator with its own 4.16 kV Class 1E switchgear bus.
During the course of an NRC inspection in September of 2001 at CGS, a finding was identified that was one of very low safety significance and was characterized as a non-cited violation.
The details of the finding are documented in NRC Inspection Report 50-397/01-06. In summary, it was found that the EDG output voltage range specified in SR 3.8.1.19.c.3 is from 3740V to 4400V and the degraded emergency bus voltage instrumentation allowable value range specified in Loss Of Power (LOP) Instrumentation Table 3.3.8.1-1.1.e is from 3685V to 3755V. This presents a condition wherein the TS allow a steady-state minimum EDG output voltage that is 15V lower than the maximum setpoint at which degraded voltage instruments may be actuated to perform their safety function.
To reconcile the overlap between the two allowable ranges and provide consistent allowable output voltage ranges for all EDGs, the licensee proposes to increase the minimum steady-state EDG output voltage limit to 3910V for the Division 1, 2 and 3 EDGs.
3.0 TECHNICAL EVALUATION
The three EDGs at CGS specify the minimum steady-state output voltage for a loaded EDG to be 3740 V. This is based on American National Standard Institute (ANSI) Standard C84.1-1970 for normal utilization voltage for a 4kV medium voltage distribution system. However, if the degraded voltage instruments are set near the upper end of their acceptable range and the output voltage of the Division 1 and Division 2 diesels (EDG 1, EDG 2) is at the lower end of the acceptable range, the degraded voltage instrumentation could actuate and trip all loads off the Division 1 and Division 2 critical buses during a loss of offsite power and/or a loss of coolant accident.
Critical bus loads include residual heat removal pumps, low pressure core spray pumps, service water pumps, and other equipment necessary to mitigate accident conditions.
The licensee proposes to use 3910V as a minimum steady-state EDG output voltage for all three EDGs. This value is the minimum voltage necessary to meet the breaker closure (ready to load) interlock for EDG 1 and EDG 2, and it is the minimum EDG output voltage specified by the TS for unloaded EDGs. This proposed new steady-state voltage will be used in TS SRs 3.8.1.2.b, 3.8.1.7.b, 3.8.1.11.c.3, 3.8.1.12.a, 3.8.1.15.b, 3.8.1.19.c.3 and 3.8.1.20 that currently specify a minimum steady-state output voltage of 3740V. This will reconcile the overlap between the two allowable ranges and is acceptable.
EDG 3 is different in that it uses an 850 RPM speed interlock for its breaker closure permissive.
However, it is reasonable to select 3910 V as an appropriate minimum steady-state voltage for EDG 3 since it is a dedicated power source for only one engineered safety feature load, and its bus voltage does not fluctuate as loads are sequenced on. Additionally, changing the minimum steady-state voltage specification for EDG 3 to 3910V (or 94 percent of a nominal 4160V) provides more margin to the analytical limit for the degraded voltage relay dropout and ensures that the EDG supplies a more conservative voltage to start the high pressure core spray pump
motor (75 percent voltage is the minimum specified voltage needed at the motor terminals to start and accelerate the pump motor). This is acceptable.
The staff finds that the proposed change is conservative and does not involve a design change or physical change to the equipment or the actual performance parameters of the diesel generators. There will be no change in the method of operation or in the way operability is demonstrated. The designs of CGSs EDGs feature precise regulation of output voltage using a Class 1E static exciter voltage regulator that controls generator output voltage to within +/-1%
of its setpoint and the setpoint for the loss of power instrumentation is also controlled to within
+/-1%. The proposed amendment does not involve a change to the margin between these two parameters and therefore is acceptable.
The AC systems will continue to perform their safety functions in accordance with GDC-17.
The changes will maintain the necessary level of systems reliability as it reconciles the overlap between the two allowable ranges of the degraded voltage instrumentation and the minimum steady-state EDGs output voltage. Therefore, the proposed changes to the technical specifications are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Washington State Official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 53985). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Saba Date: November 14, 2002